US10699818B2 - Heat exchange medium, heat exchange system, and nuclear reactor system - Google Patents

Heat exchange medium, heat exchange system, and nuclear reactor system Download PDF

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Publication number
US10699818B2
US10699818B2 US14/415,460 US201314415460A US10699818B2 US 10699818 B2 US10699818 B2 US 10699818B2 US 201314415460 A US201314415460 A US 201314415460A US 10699818 B2 US10699818 B2 US 10699818B2
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Prior art keywords
heat exchange
heat exchanger
solid particles
fluid
exchange medium
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US20150200024A1 (en
Inventor
Wenlong Zhan
Lei Yang
Hushan Xu
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Institute of Modern Physics of CAS
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Institute of Modern Physics of CAS
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
    • C—CHEMISTRY; METALLURGY
    • C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
    • C09K—MATERIALS FOR MISCELLANEOUS APPLICATIONS, NOT PROVIDED FOR ELSEWHERE
    • C09K5/00—Heat-transfer, heat-exchange or heat-storage materials, e.g. refrigerants; Materials for the production of heat or cold by chemical reactions other than by combustion
    • C09K5/08—Materials not undergoing a change of physical state when used
    • C09K5/10—Liquid materials
    • C—CHEMISTRY; METALLURGY
    • C09—DYES; PAINTS; POLISHES; NATURAL RESINS; ADHESIVES; COMPOSITIONS NOT OTHERWISE PROVIDED FOR; APPLICATIONS OF MATERIALS NOT OTHERWISE PROVIDED FOR
    • C09K—MATERIALS FOR MISCELLANEOUS APPLICATIONS, NOT PROVIDED FOR ELSEWHERE
    • C09K5/00—Heat-transfer, heat-exchange or heat-storage materials, e.g. refrigerants; Materials for the production of heat or cold by chemical reactions other than by combustion
    • C09K5/08—Materials not undergoing a change of physical state when used
    • C09K5/14—Solid materials, e.g. powdery or granular
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors
    • Y02E30/40—

Definitions

  • the present invention relates to a heat exchange medium, a heat exchange system, and a nuclear reactor system.
  • water, gas or liquid metal/molten salt is used as a cooling medium for a reactor.
  • Effective and safe heat exchange has always been important in design for an ultra-fast neutron spectrum and an extremely high power. It has always been a main target of the design of the reactor how to effectively carry away heat through a heat exchange medium in time, maintain a safe and stable operation of a system, and reduce requirements for structural material in the design in a high heat flux environment.
  • An object of the present invention is to provide a heat exchange medium, a heat exchange system, and a nuclear reactor system, which can considerably improve a heat exchange effect to solve the problem of carrying away heat at a high temperature and a high heat density.
  • a heat exchange medium comprising solid particles and a fluid.
  • the solid particles have a particle diameter of from 10 ⁇ m to 10 mm.
  • the fluid includes at least one of a gas and a liquid.
  • the fluid includes helium gas or carbon dioxide.
  • the solid particles have a density greater than that of the fluid.
  • the solid particles are made of at least one of beryllium, beryllium alloy, zirconium, zirconium alloy, titanium alloy, beryllium oxide, MAX phase material, silicon carbide, and graphite.
  • the heat exchange medium is configured to form a gas-solid two-phase flow or a liquid-solid two-phase flow.
  • the solid particles have at least one of a spherical shape, an ellipsoidal shape, and a polyhedral shape.
  • a heat exchange system comprising: the abovementioned heat exchange medium, a loop, a first heat exchanger disposed in the loop, a second heat exchanger disposed in the hoop, and a heat exchange medium conveying device configured to circulate the heat exchange medium through the first heat exchanger and the second heat exchanger in the loop.
  • a heat exchange system comprising: the abovementioned heat exchange medium, a first heat exchanger, a mixing device disposed upstream of the first heat exchanger and configured to mix the solid particles and the fluid of the heat exchange medium and convey the mixed heat exchange medium to the first heat exchanger, a separating device disposed downstream of the first heat exchanger and configured to separate the solid particles from the fluid in the heat exchange medium discharged by the first heat exchanger, a second heat exchanger, and a first conveying device configured to convey the solid particles separated by the separating device to the mixing device after having passed the separated solid particles through the second heat exchanger.
  • the heat exchange system further comprises: a third heat exchanger, and a second conveying device configured to convey the fluid separated by the separating device to the mixing device after having passed the separated fluid through the third heat exchanger.
  • the first heat exchanger comprises a barrel in which a heat exchange medium channel is formed.
  • the second heat exchanger comprises a barrel and a partition plate which is disposed in the barrel and which divides an inner chamber of the barrel into a plurality of heat exchange medium channels.
  • the heat exchange system further comprises a solid particle screening device disposed downstream of the separating device and configured to remove those of the solid particles having a particle size less than a predetermined particle size.
  • a nuclear reactor system comprising: a nuclear reactor, and the abovementioned heat exchange system, wherein the first heat exchanger is disposed inside the nuclear reactor, and the second heat exchanger is disposed outside the nuclear reactor.
  • the gas-solid or liquid-solid two-phase flow has the following advantages. For example, it has a large thermal capacity, can be used with a low-pressure system, is non-corrosive, and can be processed off-line.
  • a fission reactor cooled by the gas-solid or liquid-solid two-phase cooling medium can be operated safely and reliably at a high power density or an extremely high power density.
  • FIG. 1 is a schematic view of a fission reactor system according to an embodiment of the present invention
  • FIG. 2 is a schematic structural view of a reactor core of the fission reactor system according to the embodiment of the present invention
  • FIG. 3 is a schematic structural view of a fuel rod of the reactor core of the fission reactor system according to the embodiment of the present invention.
  • FIG. 4 is a schematic structural view of a heat exchanger according to an embodiment of the present invention.
  • a nuclear reactor system 100 according to an exemplary embodiment of the present invention comprises a nuclear reactor 1 and a heat exchange system 101 .
  • the heat exchange system 101 comprises a heat exchange medium 12 , 15 , a first heat exchanger 21 , a second heat exchanger 7 , a third heat exchanger 3 , and pipes connecting these components.
  • the first heat exchanger 21 is disposed inside the nuclear reactor 1 and may be disposed inside a reactor core 10 of the nuclear reactor 1
  • the second heat exchanger 7 and the third heat exchanger 3 are disposed outside the nuclear reactor 1 .
  • the heat exchange system 101 further comprises: a mixing device 5 disposed upstream of the first heat exchanger 21 and configured to mix the solid particles 12 and the fluid 15 of the heat exchange medium and convey the mixed heat exchange medium to the first heat exchanger 21 , a separating device 2 disposed downstream of the first heat exchanger 21 and configured to separate the solid particles 12 from the fluid 15 in the heat exchange medium 12 , 15 discharged by the first heat exchanger 21 , and a first conveying device 8 configured to convey the solid particles 12 separated by the separating device 2 to the mixing device 5 after having passed the separated solid particles 12 through the second heat exchanger 7 .
  • the heat exchange medium such as a gas-solid two-phase cooling medium flows through a fuel layer or the reactor core 10 via a heat exchange medium flow path to carry away heat generated by nuclear fuel.
  • nuclear fuel is placed in a fuel containing chamber 13 of the fuel rod 11 in the reactor core 10 .
  • the nuclear reactor 1 may be any appropriate nuclear reactor 1 such as a subcritical reactor with a blanket.
  • the separating device 2 may be any appropriate separating device such as a gravity separator and a centrifugal separator. Furthermore, dust in the heat exchange medium can also be separated by the separating device 2 .
  • the heat exchange system 101 may further comprise: a third heat exchanger 3 , and a second conveying device 23 configured to convey the fluid 15 separated by the separating device to the mixing device 5 after having passed the separated fluid 15 through the third heat exchanger 3 .
  • the second conveying device 23 may be any appropriate fluid conveying device, for example, a pump such as a gas pump or a liquid pump.
  • the third heat exchanger 3 may be any appropriate fluid heat exchanger.
  • the heat exchange system 101 may further comprise: a fluid loop 4 , and a heat exchange medium injection device disposed downstream of the mixing device 5 .
  • the heat exchange medium injection device may be for example a funnel-shaped component or any other appreciate heat exchange medium drive device such as a pump.
  • the heat exchange system 101 may further comprise: a flow rate adjustment device disposed downstream of the mixing device 5 .
  • the flow rate adjustment device may be a slideable gate which is mounted to the funnel-shaped member and which is driven by a linear motor.
  • the linear motor may be controlled by a controller.
  • the first conveying device 8 is a solid particle lifting device.
  • the first conveying device 8 may be any appropriate solid particle conveying device or a bulk material conveying device, for example, a screw type solid particle conveyer or a pneumatic type solid particle conveyer.
  • the first heat exchanger 21 comprises a barrel 25 in which a heat exchange medium channel 26 is formed.
  • the second heat exchanger 7 comprises a barrel 14 and a partition plate 27 .
  • the partition plate 27 is disposed in the barrel 14 and divides an inner chamber of the barrel 14 into a plurality of heat exchange medium channels 29 .
  • any of the first heat exchanger 21 and the second heat exchanger 7 may have one of the structures shown in FIGS. 3 and 4 .
  • the first heat exchanger 21 and the second heat exchanger 7 may also have any other appreciate structure.
  • the heat exchange system 100 may further comprise a solid particle screening device 6 disposed downstream of the separating device 2 and configured to remove those of the solid particles 12 having a particle size less than a predetermined particle size, for example, fragments in the solid particles or fine dust.
  • the solid particle screening device 6 may be a mesh screen, a centrifugal separator, a gravity separator and the like.
  • the heat exchange system 100 may not comprise the mixing device 5 , the separating device 2 , the third heat exchanger 3 , the second conveying device 23 and the pipe 4 , but comprises only the first heat exchanger 21 , the second heat exchanger 7 , and the first conveying device 8 .
  • the heat exchange system comprises: the heat exchange medium 12 , 15 , the loop 31 , the first heat exchanger 21 disposed in the loop 31 , the second heat exchanger 7 disposed in the loop 31 , and the heat exchange medium conveying device 8 configured to circulate the heat exchange medium 12 , 15 through the first heat exchanger 21 and the second heat exchanger 7 in the loop 31 .
  • a pressure in the first heat exchanger 21 of the heat exchange system 100 may be less than 1 MPa.
  • the heat exchange medium according to embodiments of the present invention can effectively improve a cooling efficiency.
  • the gas pressure of the entire system can be reduced so that the system can operate more safely and reliably.
  • the fission reactor in which the heat exchange medium according to embodiments of the present invention is used is suitable for a fast neutron spectrum or an ultra-fast neutron spectrum. The high-power density requirement can be satisfied.
  • Uranium 235, thorium, uranium 238, a long-lived fission product, and a transuranium element can be used as a nuclear fuel. And, it can be used for transmutation of spent nuclear fuel and production of isotope.
  • the heat exchange medium comprises: the solid particles 12 and the fluid 15 .
  • the solid particles 12 may have a particle diameter of from 10 ⁇ m to 10 mm. In accordance with actual requirements, the solid particles 12 may also have a particle diameter greater than or equal to 10 mm or less than or equal to 10 ⁇ m, or else, may also have a particle diameter of from 100 ⁇ m to 10 mm.
  • the particle diameters of all of the solid particles 12 may be substantially the same or different from one another, or may be substantially within a range.
  • the fluid in the heat exchange medium may include at least one of a gas and a liquid.
  • the fluid includes a gas or a liquid.
  • the gas for a high-temperature reactor may be a helium gas, and the gas for a low-temperature reactor may be carbon dioxide.
  • the fluid may also be solid at a normal atmospheric temperature, but is a liquid fluid at an operation temperature.
  • the fluid may also be any other fluids that can form a two-phase flow together with the solid particles or that can drive the solid particles to move.
  • the solid particles may be made of at least one of metal, metallic compound, ceramic material, and graphite.
  • the solid particles are made of at least one of beryllium, beryllium alloy, zirconium, zirconium alloy, titanium alloy, beryllium oxide, MAX phase material, silicon carbide, and graphite.
  • the solid particles may also be made of any other appropriate materials.
  • the solid particles may have any appropriate shape such as any regular shapes or any irregular shapes.
  • the solid particles may have at least one of a spherical shape, an ellipsoidal shape, and a polyhedral shape.
  • the solid particles may have a density greater than that of the fluid such as a liquid or a gas.
  • the heat exchange medium may be configured to form a gas-solid two-phase flow or a liquid-solid two-phase flow.
  • the heat exchange medium may form a gas-solid two-phase flow or a liquid-solid two-phase flow. Therefore, any appropriate device for conveying the gas-solid two-phase flow or the liquid-solid two-phase flow may be used to convey the heat exchange medium.
  • the solid particles 12 are stacked to form a ball bed structure having certain porosity, and move at a flow rate; while the fluid fills within gaps among the solid particles 12 and moves at another flow rate.
  • the two-phase heat exchange medium can enhance a heat exchange effect by the following four main ways of: improving a heat capacity per unit volume, improving a thermal conductivity, improving a heat transfer coefficient, and enhancing radiative heat transfer.
  • the heat exchange medium such as the gas-solid two-phase cooling medium, can carry out a better heat exchange and achieve a greater cooling of the system structure in situations where the enhanced heat exchange is required.
  • solid material having good thermal conductivity and heat capacity per unit volume may be selected as the solid particles 12 in the heat exchange medium.
  • beryllium and beryllium alloy, zirconium alloy and compound of zirconium, or titanium alloy and compound of titanium, or the like may be used.
  • a fluid having a good fluidity but a smaller density than the solid particles may be selected as the fluid of the heat exchange medium, and such fluid includes, but is not limited to, helium gas, carbon dioxide and the like.
  • the gas-solid two-phase heat exchange medium flows through the reactor core 10 via a heat exchange medium flow path, to carry away heat generated by nuclear fuel.
  • the gas-solid two-phase heat exchange medium can carry away such a great quantity of heat from the reactor core so as to improve a neutron flux in the reactor core.
  • the gas and the solid particles in the gas-solid two-phase heat exchange medium are separated by a separating device 2 such as a gas-solid particle separating device.
  • the gas After the separating, the gas enters the gas flow path 4 in which the second conveying device 23 such as a pump is disposed to drive and convey the gas, and then the heat in the gas is carried away by passing through a gas heat exchanger 7 having a cooling loop 9 .
  • the gas is then conveyed to the mixing device 5 such as a gas-solid particle mixing device.
  • the solid particles 12 reach the second heat exchanger 7 through an inclined conveying channel. In the second heat exchanger 7 , the remaining heat in the solid particles 12 is carried away through a cooling loop 9 .
  • the solid particles 12 are re-injected into the mixing device 5 such as a gas-solid particle mixing device by the first conveying device 8 such as a mechanical or pneumatic lifting conveying system, so as to re-form the gas-solid two-phase heat exchange medium.
  • a standard fluidized bed mixer may be used as the gas-solid particle mixing device.
  • the gas passes through the gaps among the solid particles, the solid particles are driven to seethe, and when a flow speed of the gas reaches or exceeds a critical fluidizing velocity of the solid particles, the solid particles exhibit a fluidity similar to that of a liquid.
  • heat carried away by the cooling loop 9 can be used to drive a generator to generate electric power.
  • the heat exchange medium according to embodiments of the present invention such as the gas-solid two-phase heat exchange medium, may be driven in such a way that the fluid and the solid particles are separately driven.
  • a conventional fluid driving apparatus may be used for driving the fluid, and there are also mature industrial designs and products used for driving the solid particles.
  • the heat exchange medium according to embodiments of the present invention such as the gas-solid two-phase heat exchange medium, may be driven in such a way that the fluid and the solid particles are driven together.
  • the heat exchange medium according to embodiments of the present invention such as the gas-solid two-phase cooling medium, has the following advantages. For example, it has a large thermal capacity, can be used with a low-pressure system, is non-corrosive, and can be processed off-line. In addition, mature subsystems in the engineering application, such as a low-pressure gas system and a solid particle conveying system, may be used as the system structure and components.
  • a fission reactor cooled by the heat exchange medium according to embodiments of the present invention can be operated safely and reliably at a high power density or at an extremely high power density.
  • uranium 235, thorium, uranium 238, long-lived fission product, and transuranium element can be used as nuclear fuels, in addition to conventional nuclear fuels.
  • the fission reactor according to embodiments of the present invention can be used for generation of energy source, transmutation of spent nuclear fuel, production of isotope, and irradiation of material.

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  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Combustion & Propulsion (AREA)
  • Thermal Sciences (AREA)
  • Materials Engineering (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
US14/415,460 2013-05-07 2013-05-07 Heat exchange medium, heat exchange system, and nuclear reactor system Active 2034-11-09 US10699818B2 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/CN2013/075266 WO2014179935A1 (zh) 2013-05-07 2013-05-07 热交换介质、热交换系统及核反应堆系统

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EP (1) EP2862912B1 (zh)
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WO (1) WO2014179935A1 (zh)

Citations (22)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB824377A (en) * 1956-12-20 1959-11-25 Gen Electric Co Ltd Improvements in or relating to nuclear reactor arrangements
GB855859A (en) 1956-02-17 1960-12-07 Vickers Electrical Co Ltd Improvements relating to nuclear reactors
US3033773A (en) 1960-03-29 1962-05-08 Donald C Schluderberg Solid gas suspension nuclear fuel assembly
US3039948A (en) * 1958-03-14 1962-06-19 Krucoff Darwin Nuclear reactor with powdered fuel
US3900366A (en) * 1973-04-02 1975-08-19 Hitachi Ltd Emergency cooling apparatus for reactors
JPS58110988A (ja) 1981-12-24 1983-07-01 Mitsui Eng & Shipbuild Co Ltd 粒子循環式熱交換装置
JPH08338892A (ja) 1995-06-14 1996-12-24 Japan Atom Energy Res Inst ヘリウム冷却高温ガス炉
CN1329123A (zh) 2000-06-15 2002-01-02 南京理工大学 纳米流体高效传热冷却工质及其制备方法
CN1422931A (zh) 2001-11-23 2003-06-11 成都奥能知科技有限公司 超热增能传热工质及其传热元件
WO2004033980A1 (ja) 2002-10-10 2004-04-22 Iseya Manufacturing Co. 固体と流体との間の熱伝達方法及び熱交換システム
JP2006045492A (ja) 2004-02-04 2006-02-16 Sk Kaken Co Ltd 蓄熱断熱体
JP2006263681A (ja) 2005-03-25 2006-10-05 Mitsubishi Paper Mills Ltd マイクロカプセル造粒物及びその利用方法
CN101285657A (zh) 2007-04-09 2008-10-15 李建民 超临界流体的流态化强化传热方法及其传热工作介质和应用
JP2008547233A (ja) 2005-06-27 2008-12-25 ユニベルシテ ピエール エ マリー キュリー ミリメートルスケールの磁性粒子を含有する導電性流体
CN101549394A (zh) 2008-04-02 2009-10-07 比亚迪股份有限公司 一种温度控制方法
CN101720488A (zh) 2007-03-06 2010-06-02 阿海珐有限公司 在应急系统的闭合回路中使用纳米颗粒的核电设备及相关方法
US20110240261A1 (en) 2008-12-19 2011-10-06 Upm-Kymmene Corporation Method for heat exchange, system and use
WO2012052661A2 (fr) 2010-10-20 2012-04-26 Centre National De La Recherche Scientifique Dispositif collecteur d'energie solaire
US20120125590A1 (en) 2009-06-18 2012-05-24 Sgl Carbon Se Temperature control medium and temperature control method
CN102568624A (zh) 2011-12-05 2012-07-11 李正蔚 高温超临界核反应堆
CN102782079A (zh) 2009-12-03 2012-11-14 原子能和替代能源委员会 氧化铝的胶态分散体
WO2013053442A1 (en) 2011-10-14 2013-04-18 Merck Patent Gmbh Thermally conductive self-supporting sheet

Patent Citations (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB855859A (en) 1956-02-17 1960-12-07 Vickers Electrical Co Ltd Improvements relating to nuclear reactors
GB824377A (en) * 1956-12-20 1959-11-25 Gen Electric Co Ltd Improvements in or relating to nuclear reactor arrangements
US3039948A (en) * 1958-03-14 1962-06-19 Krucoff Darwin Nuclear reactor with powdered fuel
US3033773A (en) 1960-03-29 1962-05-08 Donald C Schluderberg Solid gas suspension nuclear fuel assembly
US3900366A (en) * 1973-04-02 1975-08-19 Hitachi Ltd Emergency cooling apparatus for reactors
JPS58110988A (ja) 1981-12-24 1983-07-01 Mitsui Eng & Shipbuild Co Ltd 粒子循環式熱交換装置
JPH08338892A (ja) 1995-06-14 1996-12-24 Japan Atom Energy Res Inst ヘリウム冷却高温ガス炉
CN1329123A (zh) 2000-06-15 2002-01-02 南京理工大学 纳米流体高效传热冷却工质及其制备方法
CN1422931A (zh) 2001-11-23 2003-06-11 成都奥能知科技有限公司 超热增能传热工质及其传热元件
WO2004033980A1 (ja) 2002-10-10 2004-04-22 Iseya Manufacturing Co. 固体と流体との間の熱伝達方法及び熱交換システム
JP2006045492A (ja) 2004-02-04 2006-02-16 Sk Kaken Co Ltd 蓄熱断熱体
JP2006263681A (ja) 2005-03-25 2006-10-05 Mitsubishi Paper Mills Ltd マイクロカプセル造粒物及びその利用方法
JP2008547233A (ja) 2005-06-27 2008-12-25 ユニベルシテ ピエール エ マリー キュリー ミリメートルスケールの磁性粒子を含有する導電性流体
US20090173907A1 (en) 2005-06-27 2009-07-09 Emmanuelle Dubois Conducting Fluid Containing Millimetric Magnetic Particles
CN101720488A (zh) 2007-03-06 2010-06-02 阿海珐有限公司 在应急系统的闭合回路中使用纳米颗粒的核电设备及相关方法
CN101285657A (zh) 2007-04-09 2008-10-15 李建民 超临界流体的流态化强化传热方法及其传热工作介质和应用
CN101549394A (zh) 2008-04-02 2009-10-07 比亚迪股份有限公司 一种温度控制方法
US20110240261A1 (en) 2008-12-19 2011-10-06 Upm-Kymmene Corporation Method for heat exchange, system and use
US20120125590A1 (en) 2009-06-18 2012-05-24 Sgl Carbon Se Temperature control medium and temperature control method
JP2012530161A (ja) 2009-06-18 2012-11-29 エスゲーエル カーボン ソシエタス ヨーロピア 温度制御媒体
CN102782079A (zh) 2009-12-03 2012-11-14 原子能和替代能源委员会 氧化铝的胶态分散体
WO2012052661A2 (fr) 2010-10-20 2012-04-26 Centre National De La Recherche Scientifique Dispositif collecteur d'energie solaire
WO2013053442A1 (en) 2011-10-14 2013-04-18 Merck Patent Gmbh Thermally conductive self-supporting sheet
CN102568624A (zh) 2011-12-05 2012-07-11 李正蔚 高温超临界核反应堆

Non-Patent Citations (8)

* Cited by examiner, † Cited by third party
Title
English Translation of International Search Report, PCT/CN2013/075266.
English Translation of Office Action, dated Jan. 22, 2016 in counterpart Japanese Patent Application No. 2015-521949.
English Translation of Office Action, dated Nov. 15, 2014, SIPO of China in counterpart Chinese Application No. 201310164940.X.
Extended European Search Report, dated Feb. 4, 2016 in counterpart European Patent Application No. 13884084.8.
International Search Report, PCT/CN2013/075266.
Office Action, dated Jan. 22, 2016 in counterpart Japanese Patent Application No. 2015-521949.
Office Action, dated Nov. 15, 2014, SIPO of China in counterpart Chinese Application No. 201310164940.X.
Written Opinion of International Search Report, PCT/CN2013/075266.

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US20150200024A1 (en) 2015-07-16
EP2862912B1 (en) 2018-10-17
EP2862912A1 (en) 2015-04-22
WO2014179935A1 (zh) 2014-11-13
JP6049112B2 (ja) 2016-12-21
EP2862912A4 (en) 2016-03-09
JP2015524862A (ja) 2015-08-27

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